Ageing Management for Nuclear Fuel Cycle Facilities  
Published by International Atomic Energy Agency
Publication Date:  Available in all formats
ISBN: 9789201147233
Pages: 0

EBOOK (EPUB)

ISBN: 9789201147233 Price: INR 3163.99
Add to cart Buy Now
The ageing of structures, systems and components is one of the major challenges faced by nuclear fuel cycle facilities worldwide. This publication is intended to provide information on methods, approaches, practices and strategies for ageing management of nuclear fuel cycle facilities. It provides practical information on the establishment of effective ageing management programmes for nuclear fuel cycle facilities in the operational stage and on ageing management considerations in different stages in the lifetime of a nuclear fuel cycle facility. It also addresses the interface of ageing management with other technical areas and programmes, including maintenance, periodic testing and inspection, equipment qualification and configuration management. Best practice examples on how Member States are addressing ageing issues in nuclear fuel cycle facilities are also provided in this publication.
Rating
Description
The ageing of structures, systems and components is one of the major challenges faced by nuclear fuel cycle facilities worldwide. This publication is intended to provide information on methods, approaches, practices and strategies for ageing management of nuclear fuel cycle facilities. It provides practical information on the establishment of effective ageing management programmes for nuclear fuel cycle facilities in the operational stage and on ageing management considerations in different stages in the lifetime of a nuclear fuel cycle facility. It also addresses the interface of ageing management with other technical areas and programmes, including maintenance, periodic testing and inspection, equipment qualification and configuration management. Best practice examples on how Member States are addressing ageing issues in nuclear fuel cycle facilities are also provided in this publication.
Table of contents
  • 1. INTRODUCTION
    • 1.1. Background
    • 1.2. Objective
    • 1.3. Scope
    • 1.4. Structure
  • 2. AGEING AND SAFETY OF NUCLEAR FUEL CYCLE FACILITIES
    • 2.1. Ageing
      • 2.1.1. Physical ageing
      • 2.1.2. Non-physical ageing
    • 2.2. Ageing management
    • 2.3. Ageing and defence in depth
    • 2.4. Service conditions and ageing
      • 2.4.1. Normal operation
      • 2.4.2. Anticipated operational occurrences
      • 2.4.3. Environmental conditions
  • 3. AGEING MANAGEMENT CONSIDERATIONS at DIFFERENT STAGES IN THE LIFETIME OF A NUCLEAR FUEL CYCLE FACILITY
    • 3.1. Ageing management considerations in design of a nuclear fuel cycle facility
    • 3.2. Ageing management considerations in construction of a nuclear fuel cycle facility
    • 3.3. Ageing management considerations in the commissioning of a nuclear fuel cycle facility
    • 3.4. Ageing management considerations in the operation of a nuclear fuel cycle facility
      • 3.4.1. Other considerations
    • 3.5. Ageing management considerations before decommissioning
  • 4. AGEING MANAGEMENT PROGRAMME FOR NUCLEAR FUEL CYCLE FACILITIES
    • 4.1. Identification of sscs for ageing management
    • 4.2. Identification and understanding of ageing
    • 4.3. Minimization of ageing effects
    • 4.4. Detection, monitoring and trending of ageing
      • 4.4.1. Performance tests
      • 4.4.2. Non-destructive testing
      • 4.4.3. Monitoring
      • 4.4.4. Trending
    • 4.5. Acceptance criteria
    • 4.6. Mitigation of ageing
    • 4.7. Feedback from operating experience and other r&d results on ageing
    • 4.8. Documentation of ageing management
  • 5. MANAGEMENT OF OBSOLESCENCE
    • 5.1. Changes in technology
    • 5.2. Changes in safety requirements
    • 5.3. Obsolescence of knowledge
  • 6. INTERFACES WITH OTHER PROGRAMMES AND TECHNICAL AREAS
    • 6.1. Interface between ageing management and maintenance, periodic testing and inspection
    • 6.2. Interface between ageing management and safety assessment
    • 6.3. Interface between ageing management and periodic safety review
    • 6.4. Interface between ageing management and equipment qualification
    • 6.5. Interface between ageing management and configuration management
    • 6.6. Interface between ageing management and lifetime extension of a nuclear fuel cycle facility
  • 7. MANAGEMENT SYSTEM
    • 7.1. Management responsibility
    • 7.2. Resource management
    • 7.3. Process implementation
    • 7.4. Measurement, assessment and improvement
  • REFERENCES
  • Annex I EXAMPLES OF AGEING OF SSCs OF IN NUCLEAR FUEL CYCLE FACILITIES
  • Annex II AGEING MANAGEMENT DURING THE DESIGN STAGE FOR A DRY SPENT FUEL STORAGE FACILITY IN ARGENTINA
  • Annex III AGEING MANAGEMENT PROGRAMME FOR A NUCLEAR FUEL FABRICATION FACILITY IN ROMANIA
  • Annex IV AGEING MANAGEMENT PROGRAMME FOR A DRY SPENT FUEL STORAGE FACILITY IN UKRAINE
  • LIST OF ABBREVIATIONS
  • CONTRIBUTORS TO DRAFTING AND REVIEW
User Reviews
Rating